Quentin Le Coz

CEA Cadarache

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i-10 index

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Co-Authors

L. Zani

CEA Cadarache

Benoît Lacroix

CEA Cadarache

A. Torre

CEA Cadarache

S. Nicollet

CEA Cadarache

François Bonne

CEA Grenoble

F. Nunio

Commissariat à l'Énergie Atomique et aux Énergies Alternatives

R. Vallcorba

Institut de Recherche sur les Lois Fondamentales de l'Univers

V. Corato

National Agency for New Technologies, Energy and Sustainable Economic Development

D. Ciazynski

Commissariat à l'Énergie Atomique et aux Énergies Alternatives

Nicolas Misiara

Commissariat à l'Énergie Atomique et aux Énergies Alternatives

Cooperative Institutions

Commissariat à l'Énergie Atomique et aux Énergies Alternatives

National Agency for New Technologies, Energy and Sustainable Economic Development

CEA Cadarache

CEA Paris-Saclay

CEA Grenoble

Institut de Recherche sur la Fusion par Confinement Magnétique

University of Rome Tor Vergata

École Polytechnique Fédérale de Lausanne

Université Grenoble Alpes

ITER

Author Statistics

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Citation

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Updates on Magnet Design For EU-DEMO Reactor: Optimization Studies on TF and CS Systems

IEEE Transactions on Applied Superconductivity (2021)

L. Zani François Bonne V. Corato Q. Le Coz B Aguiar Jose

In the framework of EU design activities for dimensioning the future fusion DEMOnstration reactor (DEMO), extensive analyses were conducted in EUROfusion context, aiming at ultimately defining the design of the DEMO magnets system. In this objective CEA (Commissariat à l'Énergie Atomique et aux Énergies Alternatives) proposes design for both Central Solenoid (CS) and Toroidal Field (TF) cryomagnetic systems. Considering the latest DEMO reactor baseline both systems were investigated using pre-dimensioning CEA tool MADMACS, with an outcome of several options for each of them. In a second step those designs were investigated with detailed analyses (electromagnetic, thermohydraulic, mechanic). In the paper a broad analysis of the CS design considering fatigue constraints is shown, together with recommendations considering flux target. The TF system considered is an ITER-like option with radial plates and the detailed electromagnetic analysis is exposed and discussed in comparison with former methods. The outcome is used for a thermohydraulic detailed static analysis and a mechanical analysis of TF winding pack is provided and discussed in terms of results but of method as well. Global considerations and recommendations will also be provided to give a first view on cryomagnetic system optimization with respect to cost merits related to both magnet systems.

Solenoid

Dimensioning

Fusion power

Toroidal field

10.1109/tasc.2021.3068560

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Citations (6)

OLYMPE, a multi-physic platform for fusion magnet design: Development status and first applications

Cryogenics (2020)

L. Zani Benoît Lacroix A. Torre Jean-Claude Vallet C. Berthinier

Dimensioning

10.1016/j.cryogenics.2020.103086

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Citations (9)

Optimization of the cooling capacity of the cryo-magnetic system for EU DEMO at the pre-conceptual design phase

Fusion Engineering and Design (2019)

François Bonne Christine Hoa Q. Le Coz L. Zani Benoît Lacroix

Cooling capacity

Conceptual design

Cryogenics

10.1016/j.fusengdes.2019.04.028

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Citations (7)

Parametric study and optimization of the cryo-magnetic system for EU DEMO at the pre-conceptual design phase

Cryogenics (2022)

Christine Hoa Thomas Latella François Bonne Benoît Lacroix Q. Le Coz

Solenoid

Mass flow rate

Mass flow

10.1016/j.cryogenics.2022.103475

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Citations (1)

Development of a multi-physic platform OLYMPE for magnet fusion design: Progresses update and applications

Cryogenics (2022)

L. Zani François Bonne Christophe Bourcier F. Dejoie P. Hertout

Electromagnetics

10.1016/j.cryogenics.2022.103479

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Citations (4)

Model-based minimization algorithm of a supercritical helium loop consumption subject to operational constraints

IOP Conference Series Materials Science and Engineering (2017)

François Bonne P. Bonnay Alain Girard C. Hoa Benoît Lacroix

Supercritical helium loops at 4.2 K are the baseline cooling strategy of tokamaks superconducting magnets (JT-60SA, ITER, DEMO, etc.). This loops work with cryogenic circulators that force a supercritical helium flow through the superconducting magnets in order that the temperature stay below the working range all along their length. This paper shows that a supercritical helium loop associated with a saturated liquid helium bath can satisfy temperature constraints in different ways (playing on bath temperature and on the supercritical flow), but that only one is optimal from an energy point of view (every Watt consumed at 4.2 K consumes at least 220 W of electrical power). To find the optimal operational conditions, an algorithm capable of minimizing an objective function (energy consumption at 5 bar, 5 K) subject to constraints has been written. This algorithm works with a supercritical loop model realized with the Simcryogenics [2] library. This article describes the model used and the results of constrained optimization. It will be possible to see that the changes in operating point on the temperature of the magnet (e.g. in case of a change in the plasma configuration) involves large changes on the cryodistribution optimal operating point. Recommendations will be made to ensure that the energetic consumption is kept as low as possible despite the changing operating point. This work is partially supported by EUROfusion Consortium through the Euratom Research and Training Program 20142018 under Grant 633053.

Operating point

10.1088/1757-899x/278/1/012116

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Citations (1)

AC Losses in JT-60SA TF Magnet During Commissioning: Experimental Analysis and Modeling

IEEE Transactions on Applied Superconductivity (2022)

A. Louzguiti S. Davis Kazuma Fukui K. Hamada C. Hoa

During the integrated commissioning of JT-60SA tokamak, the Toroidal Field (TF) magnet has experienced fast current discharges which have induced AC losses in its winding packs (WP) and in its casings. Using the thermo-hydraulic sensors network installed at the inlet and outlet of the TF coils, we have performed enthalpy balances to estimate the transient heat loads generated by AC losses. In parallel, we have modeled the hysteresis and coupling losses produced in the WP and the eddy currents losses produced in the casings by such events. We then assess and discuss the consistency between these experimental and first theoretical analyses from the energy balance point of view.

Transient (computer programming)

10.1109/tasc.2022.3170291

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Citations (3)

Numerical Modeling of the Quench Propagation Phase in the JT-60SA TF Coils

IEEE Transactions on Applied Superconductivity (2018)

Yawei Huang Walid Abdel Maksoud Bertrand Baudouy D. Ciazynski P. Decool

In the framework of the European-Japanese project JT-60SA, the quench tests are performed for each of the 18 NbTi superconducting tokamak toroidal field coils (TFC) in the Cold Test Facility at the CEA Saclay, Gif-sur-Yvette, France. While launching these experimental quench tests, the conductor current sharing temperature (T _cs ) is reached by progressively increasing the inlet helium temperature. The quite complex quench dynamics are then observed due to several coupled physical phenomena influencing the quench propagation. In order to better understand the experimental analyses on coils quench behavior, a numerical model has been used, combining the computation code thermal hydraulic and electric analysis of superconducting cables for the longitudinal quench transient modeling along the cable-in-conduit conductor, and an additional interturn thermal coupling model for transverse heat flux modeling. In this paper, several parametric studies will be done, thanks to simplified numerical simulations in order to identify the predominant physical phenomena driving the JT-60SA TFC quench propagation. The analysis focuses on the linear power impact on the quench initiation, the quench propagation dynamics, and the reverse flow effect.

Thermal hydraulics

10.1109/tasc.2018.2799176

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Citations (3)

Studies of the CEA Design Proposals for EU-DEMO Magnets

IEEE Transactions on Applied Superconductivity (2024)

A. Torre C. Nguyen Thanh Dao Q. Le Coz P. Hertout L. Zani

The paper gives an overview of the latest magnet design activities at CEA for the EU-DEMO Magnet Systems. It explains the latest changes in design constraints, inputs and definitions, the updates that have been implemented in the design tools, and shows the latest CEA proposed design for the TF magnet. We will discuss the recent updates in the TF and PF design tools which were used in 2022 and 2023. In particular, the tools have evolved to include additional constraints or operating points like possible sub-cooling of the coils or synchronous discharge of the axisymmetric PF/CS system. The electromagnetic coupling of the TF coils with coil case and radial plates is also discussed during a fast safety discharge, along with energy extraction and deposition sharing. Furthermore, a new 2D TF mechanical model is presented that permits to make a fast iteration with design tools and optimize the radial build. Finally, the paper also includes an update on the CEA TF conductor qualification sample, describing in particular the latest results obtained in the Twente Press.

10.1109/tasc.2024.3362750

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Citations (0)

Advance in the conceptual design of the European DEMO magnet system

Superconductor Science and Technology (2020)

Kamil Sedlák V A Anvar N. Bagrets Marco Evangelos Biancolini R. Bonifetto

The European DEMO, i.e. the demonstration fusion power plant designed in the framework of the Roadmap to Fusion Electricity by the EUROfusion Consortium, is approaching the end of the pre-conceptual design phase, to be accomplished with a Gate Review in 2020, in which all DEMO subsystems will be reviewed by panels of independent experts. The latest 2018 DEMO baseline has major and minor radius of 9.1 m and 2.9 m, plasma current 17.9 MA, toroidal field on the plasma axis 5.2 T, and the peak field in the toroidal-field (TF) conductor 12.0 T. The 900 ton heavy TF coil is prepared in four low-temperature-superconductor (LTS) variants, some of them differing slightly, other significantly, from the ITER TF coil design. Two variants of the CS coils are investigated—a purely LTS one resembling the ITER CS, and a hybrid coil, in which the innermost layers made of HTS allow the designers either to increase the magnetic flux, and thus the duration of the fusion pulse, or to reduce the outer radius of the CS coil. An issue presently investigated by mechanical analyzes is the fatigue load. Two variants of the poloidal field coils are being investigated. The magnet and conductor design studies are accompanied by the experimental tests on both LTS and HTS prototype samples, covering a broad range of DC and AC tests. Testing of quench behavior of the 15 kA HTS cables, with size and layout relevant for the fusion magnets and cooled by forced flow helium, is in preparation.

Thermonuclear Fusion

Fusion power

Toroidal field

Conceptual design

10.1088/1361-6668/ab75a9

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Citations (44)